Control Theory of Atom Ratio of Oxygen and Metal for FBR MOX Fuel

QU Zhe-hao; YIN Bang-yue; YANG Qi-fa; LIANG Xue-yuan

doi:10.7538/yzk.2014.48.07.1234

Atomic Energy Science and Technology > 2014 > 48(7): 1234-1242. > DOI: 10.7538/yzk.2014.48.07.1234

QU Zhe-hao, YIN Bang-yue, YANG Qi-fa, LIANG Xue-yuan. Control Theory of Atom Ratio of Oxygen and Metal for FBR MOX Fuel[J]. Atomic Energy Science and Technology, 2014, 48(7): 1234-1242. DOI: 10.7538/yzk.2014.48.07.1234

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Control Theory of Atom Ratio of Oxygen and Metal for FBR MOX Fuel

1.
Department of Reactor Engineering Research and Design, China Institute of Atomic Energy, Beijing 102413, China
2.
Institute for Standardization of Nuclear Industry, Beijing 100091, China

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In this paper, model of oxygen potential and control theory of atom ratio of oxygen and metal (O/M ratio) for FBR MOX fuel were discussed. Blackburn model and point defect model are usually used two types of oxygen potential model of nuclear fuel, whose precision is affected by ion reaction equilibrium constant, thermodynamic data and experimental measured data. If a designed O/M ratio of 1.97 is required for (U_0.75Pu_0.25)O_2-x fuel sintered at 1 750 ℃ in 0.1 MPa Ar-5%H₂ mixture gases, oxygen partial pressure will be limited to 1.07×10^-5 Pa or oxygen potential will be limited to -386.15 kJ/mol when calculated by Blackburn model; oxygen partial pressure will be limited to 0.70×10^-5 Pa and oxygen potential will be limited to -393.22 kJ/mol when calculated by point defect model. If a designed O/M ratio of 1.95, 1.96, 1.97, 1.98, 1.99 and 1.995 is required respectively, water content in gas will be limited to 370.4, 739.8, 1 633.7, 4 403.6, 17 855.4 and 43 064.8 ppm respectively, or gas dew point will be limited to -30.10, -23.27, -14.98, -3.77, 13.83 and 26.16 ℃ respectively.

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[1]	TOCI F, MANES L, EWART F T, et al. On the determination of oxygen potentials and O/M ratios in mixed U-Pu oxides by means of solid state galvanic cells[J]. Journal of Applied Electrochemistry, 1979, 9(3): 399-401.
[2]	KUTTY T R G, HEGDE P V, KAHN K B, et al. Densification behavior of UO₂ in six different atmospheres[J]. Journal of Nuclear Materials, 2002, 305（2-3）: 159-168.
[3]	LAY K W, CARTER B E. Role of the O/U ratio on the sintering of UO2[J]. Journal of Nuclear Materials, 1969, 30（1-2）: 74-87.
[4]	HARADA Y. UO₂ sintering in controlled oxygen atmospheres of three-stage process[J]. Journal of Nuclear Materials, 1997, 245（2-3）: 217-223.
[5]	CHEVREL H, DEHAUDT P, FRANCOIS B, et al. Influence of surface phenomena during sintering of over stoichiometric uranium dioxide UO_2+x[J]. Journal of Nuclear Materials, 1992, 189（2）: 175-182.
[6]	ASSMANN H, DOERR W, PEEHS M. Oxide fuels with controlled microstructure[J]. Journal of the American Ceramic Society, 1984, 67（9）: 631-636.
[7]	FUHRMAN N, HOWER L D, HOLDEN R B. Low-temperature sintering of uranium dioxide[J]. Journal of the American Ceramic Society, 1963, 46（3）: 114-121.
[8]	唐纳德•奥兰德. 核反应堆燃料元件基本问题[M]. 北京：原子能出版社，1983：231.
[9]	RAND M H, MARKIN T L. Some thermodynamic aspects of (U, Pu)O₂ solid solutions and their use as nuclear fuels[C]∥Thermodynamics of Nuclear Materials 1967 Symposium Proceedings. Vienna: [s. n.], 1968: 637-650.
[10]	FUJINO T, SATO N, YAMADA K. A refined analysis of oxygen potential of M_yU_1-yO₂₊_x (M=M³⁺ and M²⁺) by lattice statistics based on the grand partition function and the Flory methods[J]. Journal of Nuclear Materials, 1995, 223（1）: 6-19.
[11]	STAN M, CRISTEA P, Sr WALLACE T C. Thermochemistry of defects and oxygen diffusion in PuO_2-x[C]∥Proceedings of 11th Symposium on Thermodynamics of Nuclear Materials. Karlsruhe, Germany: [s. n.], 2004.
[12]	BLACKBURN P E, JOHNSON C E. Oxygen pressures over fast breeder reactor fuel (Ⅰ): A model for UO_2±x[J]. Journal of Nuclear Materials, 1973, 46（3）: 244-252.
[13]	梁雪元. MOX燃料混合工艺及热力学分析[D]. 北京：中国原子能科学研究院，2006.
[14]	STAN M. Theory-based models and simulations of materials for fusion[C]∥Fusion Power Renew Workshop. US: University of California, 2009.
[15]	HOCH M, FURMAN F J. Non-stoichiometry of UO₂-CeO₂: The system UO₂- CeO₂- CeO_1.5 at 900 to 1 200 ℃[C]∥Thermodynamics Proceedings of the Symposiumn on Thermodynamics With Emphasis on Nuclear Materials and Atomic Transport in Solids. Vienna: IAEA, 1966: 517-532.
[16]	BESMANN T M, LINDEMER T B. Chemical thermodynamic representation of UO_2±x[C]∥ Proceedings of Conference on Thermodynamics. Hamilton, Canada: [s. n.], 1984.
[17]	BESMANN T M, LINDEMER T B. Chemical thermodynamic representation of PuO_2-x and U_1-zPu_zO_w[C]∥ Proceedings of Conference on Chemical Thermodynamics and 39 Calorimetry Conference. Hamilton, Canada: [s. n.], 1984.
[18]	KRISHINAIAH M V, SRIRAMAMURTI P. Computational model for the oxygen potentials of mixed uranium-plutonium oxide[J]. Journal of the American Ceramic Society, 1984, 67（8）: 568-571.
[19]	VANA VARAMBAN S, GANESAN V, VASUDEVA RAO P R. Estimation of oxygen potential for U-Pu-O mixed oxide fuel[J]. Journal of Nuclear Materials, 2009, 389（1）: 72-77.
[20]	KATO M, NAKAMICHI S, TAKEUCHI K, et al. Measurement of oxygen potential of (U_0.8-Pu_0.2)O_2±x at 1 773 and 1 873 K, and its analysis based on point defect chemistry[J]. CALPHAD, 2011, 35（4）: 623-626.
[21]	KATO M, KONASHI K, NAKAE N. Analysis of oxygen potential of (U_0.7-Pu_0.3)O_2±x and (U_0.8-Pu_0.2)O_2±x based on point defect chemistry[J]. Journal of Nuclear Materials, 2009, 389（1）: 164-169.
[22]	KATO M. Oxygen potentials and defect chemistry in nonstoichiometric (U, Pu)O₂[R]∥Stoichiometry and Materials Science: When Numbers Matter. [S. l.]: [s. n.], 2012: 203-218.
[23]	RASMUSSEN D E, BENECKE M W, JENTZEN W R, et al. Oxygen to metal ratio control during fabrication of mixed oxide fast breeder reactor fuel pellets, HEDL-SA-1763FP[R]. Atlanta: Hanford Engineering Development Laboratory, 1979.
[24]	JAVED N A. Thermodynamic behavior of (U, Pu) mixed-oxide fuels[J]. Journal of Nuclear Materials, 1973, 47（3）: 336-344.

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